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001 ocn861495828;

003 OCoLC;

005 20131025085129.0;

006 m o d f ;

007 cr cn| ;

008 131025s2013 dcua ob f000 0 eng d;

035 a| (Sirsi) o861495828;

049 a| ERE#;

074 a| 1051-H-41 (online);

086 0 a| Y 3.N 88:53/0432;

100 1 a| Belaïd, S.,e| author.?| UNAUTHORIZED;

245 10 a| Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE /c| prepared by: S. Belaïd, J. Freixa, O. Zerkak.;

246 3 a| Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE;

264 1 a| Washington, DC :b| U.S. Nuclear Regulatory Commission,c| 2013.;

300 a| 1 online resource (xiii, 29 pages) :b| color illustrations.;

336 a| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

490 1 a| International agreement report ;v| NUREG/IA-0432;

500 a| Title from title screen (viewed Oct. 25, 2013).;

500 a| "September 2013.";

504 a| Includes bibliographical references (page 29).;

650 0 a| Pressurized water reactorsx| Emergency core cooling systemsx| Testing.=| ^A687313;

650 0 a| Nuclear fuel claddingsx| Effect of temperature onx| Measurement.=| ^A849440;

650 0 a| Nuclear power plantsx| Safety measuresx| Testing.=| ^A176090;

700 1 a| Freixa, J.,e| author.?| UNAUTHORIZED;

700 1 a| Zerkak, O.,e| author.?| UNAUTHORIZED;

710 2 a| U.S. Nuclear Regulatory Commissione| issuing body.=| ^A198030;

776 08 i| Print version:a| Belaïd, S.t| Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACEw| (OCoLC)861495775;

830 0 a| International agreement reportv| NUREG/IA-0432.=| ^A463558;

856 40 u| https://purl.fdlp.gov/GPO/gpo40912;

949 a| Click on web addressw| ASISh| JOYNER94;

998 a| 3398154;

998 a| u3398154;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 3398154-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 12/11/2013x| EDOCUMENTz| JERESOURCE;

Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / prepared by: S. Belaïd, J. Freixa, O. Zerkak.

Author/creator	Belaïd, S. author.
Other author	Freixa, J., author.
Other author	Zerkak, O., author.
Other author	U.S. Nuclear Regulatory Commission issuing body.
Format	Electronic
Publication	Washington, DC : U.S. Nuclear Regulatory Commission, 2013.
Description	1 online resource (xiii, 29 pages) : color illustrations.
Supplemental Content	https://purl.fdlp.gov/GPO/gpo40912
Subjects	Pressurized water reactors--Emergency core cooling systems. --Testing. Pressurized water reactors--Equipment and supplies. --Effect of temperature on. --Measurement. Nuclear fuel claddings--Effect of temperature on. --Measurement. Nuclear power plants--Safety measures. --Testing.

Variant title	Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE
Series	International agreement report ; NUREG/IA-0432 International agreement report NUREG/IA-0432. ^A463558
General note	Title from title screen (viewed Oct. 25, 2013).
General note	"September 2013."
Bibliography note	Includes bibliographical references (page 29).
Issued in other form	Print version: Belaïd, S. Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE
GPO item number	1051-H-41 (online)
Govt. docs number	Y 3.N 88:53/0432

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Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / prepared by: S. Belaïd, J. Freixa, O. Zerkak.

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